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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Rudolf Avenhaus, Gert Spannagel
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1003-1008
Analysis and Accountancy | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30537
Articles are hosted by Taylor and Francis Online.
Principles of material accountancy are presented for a typical tritium fuel cycle under special consideration of the in-vessel inventory which for the time being can only be estimated roughly. For this purpose we pursue the selection and testing of suitable algorithms: For the process simulation we apply the stochastic version of the Karlsruhe Tritium Model. It is demonstrated that with the help of statistical methods which have been developed three years ago for the purpose of nuclear material safeguards, the measured data can be analyzed such that questions put forward by the operator as well as the licensing authority can be answered.
